IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 1.102300+4 2.279200+1 1 0 0 17113 1451 1 0.000000+0 0.000000+0 0 0 0 07113 1451 2 0.000000+0 0.000000+0 0 0 84 137113 1451 3 11-Na- 23 ORNL EVAL-NOV79 D. C. LARSON 7113 1451 4 DIST-MAR84 840730 7113 1451 5 MF=2 7113 1451 6 RESOLVED RESONANCE REGION FROM 600 EV TO 500 KEV, 7113 1451 7 BASED ON NEUTRON DATA MAINLY OF SELTZER (SE74) AND 7113 1451 8 LARSON (LA76). BACKGROUND FILE <250 MB IS INCLUDED 7113 1451 9 GAMMA RESONANCE PARAMETERS BSSED ON DATA OF MACKLIN (MA76) 7113 1451 10 MF=3 7113 1451 11 MT=16 7113 1451 12 THIS EVALUATION IS TAKEN DIRECTLY FROM ENDF/B-V MAT 1311. 7113 1451 13 THERE ARE FOUR MAJOR DATA SETS (LI65,ME67,PA65 AND PI65) WHICH 7113 1451 14 COVER THE ENERGY RANGE FROM THRESHOLD TO 20 MEV. IN ADDITION 7113 1451 15 THERE ARE FOUR MEASUREMENTS (AR73,BA69,MA72 AND PR55) AT ONE OR 7113 1451 16 TWO ENERGIES BETWEEN 14 AND 15 MEV. THE MEASUREMENTS OF BA69, 7113 1451 17 LI65 AND PA65 ARE IN GOOD AGREEMENT WITH RESULTS OF EXTENSIVE 7113 1451 18 MODEL CALCULATIONS WHICH CONSISTENTLY REPRODUCED DATA FROM MANY 7113 1451 19 OTHER SODIUM REACTIONS. THE CALCULATED (N,2N) CROSS SECTION COULD7113 1451 20 NOT BE LOWERED (AS REQUIRED TO REPRODUCE THE OTHER (N,2N) DATA) 7113 1451 21 WITHOUT ADVERSELY AFFECTING WELL KNOWN CROSS SECTIONS FOR OTHER 7113 1451 22 REACTIONS. EVALUATION OF THE (N,2N) CROSS SECTION WAS THUS BASED 7113 1451 23 ON MODEL CALCULATIONS, IN SUBSTANTIAL AGREEMENT WITH DATA OF 7113 1451 24 BA69,LI65 AND PA65. 7113 1451 25 MT=102 TAKEN FROM ENDF/B-IV 7113 1451 26 MT=103 7113 1451 27 FOR THE (N,P) CROSS SECTION THE DATA OF WILLIAMSON (WI61) WERE 7113 1451 28 USED FROM THRESHOLD TO 5.75 MEV. FROM 5.75 TO 9.0 MEV THE DATA 7113 1451 29 OF BASS ET AL. (BA66) WERE USED, AND WI61 WAS USED AGAIN FROM 7113 1451 30 9 TO 10 MEV. NO DATA WERE AVAILABLE FROM 10 TO 14 MEV. THE 7113 1451 31 THRESHOLD OF THE (N,PN) REACTION IS 9.18 MEV, SO ABOVE THIS ENERGY7113 1451 32 THE (N,P) REACTION IS SPLIT INTO (N,PG + N,PN). FOR THE GENERAL 7113 1451 33 PURPOSE ENDF/B-V FILE, THESE ARE COMBINED INTO THE (N,P) CROSS 7113 1451 34 SECTION. THERE ARE ACTIVATION MEASUREMENTS OF THE (N,PG) 7113 1451 35 COMPONENT FROM 14 TO 20 MEV WHICH ARE IN AGREEMENT.(AL61,CS67, 7113 1451 36 FL67,KH65,MI66,PA67,PI65,PR66,WI61) EXTENSIVE MODEL CALCULATIONS 7113 1451 37 PERFORMED FOR THE SODIUM EVALUATION REPRODUCE THE (N,PG) DATA. 7113 1451 38 FOR THIS ACTIVATION FILE, ONLY THE CROSS SECTION FOR THE (N,PG) 7113 1451 39 COMPONENT IS GIVEN, SO ABOVE 11 MEV IT DIFFERS FROM THE GENERAL 7113 1451 40 PURPOSE FILE. 7113 1451 41 MF=8 AND 9 7113 1451 42 MT=16 7113 1451 43 *********** DECAY OF 22NA (FILES 8/16 AND 9/16) ************* 7113 1451 44 THESE FILES WERE PROVIDED BY C. REICH OF INEL FOR THE ENDF/B-V 7113 1451 45 EVALUATION EFFORT OF CSWEG. 7113 1451 46 THE 23NA(N,2N) REACTION LEADS TO 22NA, WHICH HAS A HALFLIFE OF 7113 1451 47 2.601 YEARS. ITS DECAY IS VIA ELECTRON CAPTURE (9.45%) AND 7113 1451 48 POSITRON EMISSION (90.55%) TO 22NE, WHICH IS A GAS. THIS RESULTS 7113 1451 49 IN TWO .511 MEV GAMMA RAYS AND A 1.27 MEV GAMMA RAY. 7113 1451 50 MT=103 7113 1451 51 ********* DECAY OF 23NE (FILES 8/103 AND 9/103) ******* 7113 1451 52 THESE FILES WERE PROVIDED BY C. REICH OF INEL FOR THE ENDF/B-V 7113 1451 53 EVALUATION EFFORT OF CSWEG. 7113 1451 54 THE 23NA(N,PG) REACTION LEADS TO 23NE, A GAS, WHICH HAS A HALFLIFE7113 1451 55 OF 37.6 SECONDS. IT BETA DECAYS BACK TO 23NA (67% TO GROUND 7113 1451 56 STATE, 32% TO THE 0.440 MEV LEVEL AND 1% TO THE 2.08 MEV LEVEL). 7113 1451 57 THE MAJOR GAMMA RAY EMISSION IS A 0.440 MEV GAMMA RAY RESULTING 7113 1451 58 FROM THE DECAY TO THE 0.440 MEV LEVEL. 7113 1451 59 ******* REFERENCES ****** 7113 1451 60 LA76 DC LARSON ET.AL ORNL-TM-5614 (1976) 7113 1451 61 MA76 RL MACKLIN ET.AL TO BE PUBLISHED 7113 1451 62 SE74 J SELTZER AND FWK FIRK NSE 53(1974) 415 7113 1451 63 AL61 D.L. ALLAN, NUCL. PHYS. 24,274 (1961) 7113 1451 64 BA66 R. BASS, P. HAUG, K. KRUGER AND B. STAGINNUS, REPORT 7113 1451 65 EANDC(U) 66, P64 (1966) 7113 1451 66 CS67 J. CSIKAI AND S. NAGY, NUCL. PHYS. A91,222 (1967) 7113 1451 67 FL67 F. FLESCH AND P. HILLE, OAW 176, 45 (1967) 7113 1451 68 KH65 C.S. KHURANA AND I.M. GOVIL, NUCL PHYS. 69,153 (1965) 7113 1451 69 MI66 B. MITRA AND A.M. GHOSE, NUCL. PHYS. 83, 157 (1966) 7113 1451 70 PA67 A. PASQUARELLI, NUCL. PHYS. A93, 218 (1967) 7113 1451 71 PI65 J. PICARD AND C. WILLIAMSON, NUCL. PHYS. 63, 673 (1965) 7113 1451 72 PR66 R. PRASAD AND D.C. SARKAR, NUCL. PHYS. 85, 476 (1966) 7113 1451 73 WI61 C.F. WILLIAMSON, PHYS. REV. 122, 1877 (1961) 7113 1451 74 AR73 J. ARAMINOWICZ AND J. DRESLER, INSTITUTE OF NUCLEAR RESEARCH 7113 1451 75 WARSAW REPORT INR-1464, P14 (1973). 7113 1451 76 BA69 R.C. BARRALL, J.A. HOLMES AND M. SILBERGELD, KIRTLAND,NEW 7113 1451 77 MEXICO, AIR FORCE WEAPONS LAB REPORT AFWL-TR-68, P134 (1969) 7113 1451 78 LI65 H. LISKIEN AND A. PAULSEN, NUCL. PHYS. 63,393 (1965) 7113 1451 79 MA72 G.N. MASLOV, F. NASYROV AND N.F. PASHKIN, OBNINSK REPORT 7113 1451 80 YK-9, P50 (1972). 7113 1451 81 ME67 H.O. MENLOVE, K.L. COOP, H.A. GRENCH AND R. SHER, PHYS. REV. 7113 1451 82 163,1299 (1967) 7113 1451 83 PA65 A. PAULSEN PRIVATE COMMUNICATION TO CCDN SACLAY (1965) CSISRS7113 1451 84 REFERENCE NUMBER 60825-002 7113 1451 85 PI65 J. PICARD AND C. WILLIAMSON, NUCL. PHYS. 63, 673 (1965). 7113 1451 86 PR55 R.J. PRESTWOOD, PHYS. REV. 98, 47 (1955). 7113 1451 87 1 451 100 17113 1451 88 2 151 30 17113 1451 89 3 16 7 17113 1451 90 3 102 16 17113 1451 91 3 103 38 17113 1451 92 8 16 3 17113 1451 93 8 102 3 17113 1451 94 8 103 5 17113 1451 95 9 16 4 17113 1451 96 9 102 4 17113 1451 97 9 103 4 17113 1451 98 33 16 8 17113 1451 99 33 103 8 17113 1451 100 0.000000+0 0.000000+0 0 0 0 07113 1 0 101 0.000000+0 0.000000+0 0 0 0 07113 0 0 102 1.102300+4 2.279200+1 0 0 1 07113 2151 103 1.102300+4 1.000000+0 0 0 1 07113 2151 104 6.000000+2 5.000000+5 1 2 0 07113 2151 105 1.500000+0 5.410000-1 0 0 3 07113 2151 106 2.279200+1 0.000000+0 0 0 24 47113 2151 107 2.810000+3 1.000000+0 3.763400+2 3.760000+2 3.530000-1 0.000000+07113 2151 108 2.429700+5 1.000000+0 3.295000+2 3.280000+2 1.500000+0 0.000000+07113 2151 109 2.983200+5 2.000000+0 2.039000+3 2.038000+3 1.020000+0 0.000000+07113 2151 110 5.385700+5 1.000000+0 6.278000+4 6.277000+4 1.014000+1 0.000000+07113 2151 111 2.279200+1 0.000000+0 1 0 72 127113 2151 112 7.617000+3 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